ML061370096
| ML061370096 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/31/2005 |
| From: | Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2010-0209 | |
| Download: ML061370096 (29) | |
Text
ENCLOSURE I OFF-SITE RADIATION DOSE ASSESSMENT FOR January 01, 2005 - December 31, 2005 8 pages follow
PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFF-SITE RADIATION DOSE ASSESSMENT FOR January through December 2005 An Assessment of the radiation dose due to releases from Prairie Island Nuclear Generating Plant during 2005 was performed in accordance with the Offsite Dose Calculation Manual as required by Technical Specifications. Computed doses were well below the 40 CFR Part 190 Standards and 10 CFR Part 50 Appendix I Guidelines.
Off-site dose calculation formulas and meteorological data from the Off-site Dose Calculation Manual were used in making this assessment. Source terms were obtained from the Annual Radioactive Effluent and Waste Disposal Report prepared for NRC review for the year of 2005.
Off-site Doses from Gaseous Release Computed doses due to gaseous releases are reported in Table 1. Critical receptor location and pathways for organ doses are reported in Table 2. Gaseous release doses are a small percentage of Appendix I Guidelines.
Off-site Doses from Liquid Release Computed doses due to liquid releases are reported in Table 1. Critical receptor information is reported in Table 2. Liquid release doses, both whole body and organ, are a small percentage of Appendix I Guidelines.
Doses to Individuals Due to Activities Inside the Site Boundary Occasionally sportsmen enter the Prairie Island site for recreational activities. These individuals are not expected to spend more than a few hours per year within the site boundary. Commercial and recreational river traffic exists through this area.
For purposes of estimating the dose due to recreational and river water transportation activities within the site boundary, it is assumed that the limiting dose within the site boundary would be received by an individual who spends a total of seven days per year on the river just off-shore from the plant buildings (ESE at 0.2 miles). The gamma dose from noble gas releases and the whole body and organ doses from the inhalation pathway due to Iodine 131, Iodine-1 33, tritium and long-lived particulates were calculated for this location and occupancy time. These doses are reported in Table 1.
ABNORMAL RELEASES There were no abnormal releases for 2005.
40CFR190 COMPLIANCE The calculated dose from the release of radioactive materials in liquid or gaseous effluents did not exceed twice the limits of 10CFR50, Appendix I, therefore compliance with 40CFR190 is not required to be assessed, in this report.
SAMPLING. ANALYSIS AND LLD REQUIREMENTS The minimum sampling frequency, minimum analysis frequency and lower limit of detection (LLD) requirements, as specified in ODCM Tables 2.1 and 3.1 were exceeded in the following instances:
- 1. SOFTWARE ISSUE CAUSES INACCURATE QUANTIFICATION OF NIOBIUM 95 Due to the parent/daughter relationship between Zirconium-95 and Niobium-95 and the fact that Nb-95 has a larger dose factor, it was decided to adjust the amount of Nb-95 identified to equal that of the Zr-95, when ever Nb-95 was present and the quantity of Zr-95 exceeded that of the Nb-95.
The software was modified to adjust the Nb-95 concentration to match the higher Zr-95 concentration.
When Nb-95 was detected in a spectrum file, the Nb-95 concentration was stored for later comparison to the Zr-95 concentration. If the sample did not contain Zr-95, the original identified Nb-95 concentration should have been added to the release spectrum file.
On October 13th, during preparation for a waste tank release it was noted that the spectrum identified Nb-95, but the Pre-Release Authorization did not include Nb-95.
From the time the software was modified until 10/13/05, the site was not calculating the amount of Nb-95 released via liquid waste tank releases whenever Nb-95 was present in the sample and Zr-95 was not present. The data transfer problem only existed when the two isotopes were at the lower edge of detection.
Cause: A programming error caused the Nb-95 to be omitted from the release file if Zr-95 was not present.
Corrective The software was modified to correct the error and tested on 10/13/05.
Action:
Results: From 1993 through 2005, there were 91 instances identified, when the Nb-95 was not correctly transferred to the effluent software. The total number of uCi released over those 91 instances was 630 uCi.
Examination of the 10CFR-20 Maximum Permissible Concentration Limits, at the point of discharge was performed. During the 13 year period of 1993 through 2005 the Maximum Permissible Concentration was not exceeded.
The dose received was 8.OE-09 mRem to the total body and 9.OE-05 mRem to the critical organ (GI-LLI).
The maximum dose received for a given year, 1996, was 1.60E-09 mRem to the total body and 1.81E-05 mRem to the critical organ (GI-LLI).
The minimum dose received for a given year, 2004, was 1.08E-l0 mRem to the total body and 1.22E-06 mRem to the critical organ (GI-LLI).
The additional dose resulting from the release of the unreported Nb-95 did not impose a risk to the Health and safety of the public.
The event was captured in the site's Action Request Process, CAP-0 1000932.
The event was reported to the NRC Region 3 RP Inspector, at the time of the event.
- 2. ODCM QUARTERLY COMPOSITE SAMPLE LOST An aliquot of sample (particulate filter) is saved from each airborne release. At the end of each quarter, a composite sample is prepared, for each release path, and shipped to a vendor for Sr-89/90 analysis.
These analyses are required by the ODCM (Offsite Dose Calculations Manual).
Some time after Quarter 2 Composite Preparation, the Spent Fuel Pool Ventilation Filters were lost.
An exhaustive search was made, but the filters were not found.
Cause: Control of the composites samples was insufficient.
Corrective The procedure controlling the compositing and storage of samples awaiting shipment Actions: was enhanced to include additional controls and to require inventories be performed by all persons handling the samples.
A storage container for the prepared samples was provided to segregate and protect prepared samples from loss.
Results: The lost samples were verified to be non-radioactive per the count performed during compositing and shipping preparation.
A review of data for all ventilation pathways for the last 3 years noted all Sr-89/90 results were less than minimum detectable activity.
A review of data for all other ventilation pathways for quarter 2 and all ventilation pathways for the subsequent quarter (quarter 3) noted all Sr-89/90 results were less than minimum detectable activity.
A value of <MDA was entered for Quarter 2 2005 Spent Fuel Pool Ventilation composite.
There was no imposition upon the health and safety of the public.
The event was captured in the site's Action Request Process, CAP-044128.
The event was reported to the NRC Region 3 RP Inspector, at the time of the event.
MONITORING INSTRUMENTATION There were no occurrences when less than the minimum required radioactive liquid and/or gaseous effluent monitoring instrumentation channels were operable as required by ODCM Tables 2.2 and 3.2.
There was a missed compensatory sample during a monitor out-of-service period.
- 1. MISSED COMPENSATORY SAMPLE DURING OUT-OF-SERVICE PERIOD FOR R-21, DISCHARGE CANAL MONITOR The ODCM Table 2.2 Action 6 requires that a grab sample be taken every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during a period when R-21, Circulating Water Discharge Canal Monitor, is out of service. On 1/8/06, during a period when R-21 was out of service, a sample was not taken as required. Upon discovery, the sample was taken at about 17.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after the last sample (5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after required).
Cause: The event was a human performance error.
Corrective The duty chemist will now coordinate with the operations crew to Action: assist in assuring compensatory sampling is performed.
Results: The sample taken indicated no activity.
Examination of other radiation monitors, including R- 18, Waste Disposal Liquid Effluent Monitor and both RI9s, Unit 1 and Unit 2 Steam Generator Blowdown Liquid Monitors, noted no increase.
No Radioactive Waste Tank Release or Steam Generator Blowdown to the river occurred during this period.
This event did not impose a risk to the Health and safety of the general public.
A department clock reset was initiated.
The event was captured in the site's Action Request Process, CAP-040479.
The event was reported to the NRC Region 3 RP Inspector, at the time of the event.
Doses to Individuals Due to Effluent Releases from the Independent Spent Fuel Storage Facility (ISFSI)
Three (3) fuel casks were loaded and placed in the storage facility during the 2005 calendar year. The total number of casks in the ISFSI is twenty (20). There has been no release of radioactive effluents from the ISFSI.
CURRENT ODCM REVISION The Offsite Dose Calculation Manual was revised in 2005. The current revision is 19. The revision date is September 12, 2005. A copy is submitted with this year's report.
PROCESS CONTROL PROGRAM There were no changes made to the Process Control Program in 2005. Current manual is revision 8, August 25, 1999.
Table 1 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND PERIOD: JANUARY through DECEMBER 2005 10 CFR Part 50 Appendix I Guidelines for a 2-unit site per year Gaseous Releases Maximum Site Boundry Gamma Air Dose (mrad) 5.54E-03 20 Maximum Site Boundry Beta Air Dose (mrad) 2.11E-02 40 Maximum Off-site Dose to any organ (mrem)* 3.77E-02 30 Offshore Location Gamma Dose (mrad) 3.78E-04 Total Body (mrem)* 1.23E-03 Organ (mrad)* 1.35E-03 30 Liquid Releases Maximum Off-site Dose Total Body (mrem) 1.33E-03 6 Maximum Off-site Dose Organ - GI TRACT (mrem) 3.21E-03 20 Limiting Organ Dose Organ - TOTAL BODY (mrem) 1.33E-03 6
Table 2 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND SUPPLEMENTAL INFORMATION PERIOD: JANUARY through DECEMBER 2005 Gaseous Releases Maximum Site Boundary Dose Location (From Building Vents)
Sector WNW Distance (miles) 0.4 Offshore Location Within Site Boundary Sector ESE Distance (miles) 0.2 Pathway Inhalation Maximum Off-site Sector SSE Distance (miles) 0.6 Pathways Plume, Ground, Inhalation, Vegetables Age Group Child Liquid Releases Maximum Off-site Dose Location Downstream Pathway Fish
ENCLOSURE 2 ANNUAL RADIOACTIVE EFFLUENT REPORT SUPPLEMENTAL INFORMATION January 01, 2005 - December 31, 2005 9 pages follow
2005 Annual Radioactive Effluent Report REV. 0 Page 1 of 9 Retention: Lifetime ANNUAL RADIOACTIVE EFFLUENT REPORT 01-JAN-05 THROUGH 31-DEC-05 SUPPLEMENTAL INFORMATION Facility: Prairie Island Nuclear Generating Plant Licensee: Northern States Power Company License Numbers: DPR-42 & DPR-60 A. Regulatory Limits
- 1. Liquid Effluents:
- a. The dose or dose commitment to an individual from radioactive materials in liquid effluents released from the site shall be limited to:
for the quarter 3.0 mrem to the total body 10.0 mrem to any organ for the year 6.0 mrem to the total body 20.0 mrem to any organ
- 2. Gaseous Effluents:
- a. The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to:
noble gases
- 500 mrem/year total body
- b. The dose due to radioactive gaseous effluents released from the site shall be limited to:
noble gases *10 mrad/quarter gamma
- 20 mrad/quarter beta
- 20 mrad/year gamma
- 30 mrem/year to any organ
2005 Annual Radioactive Effluent Report Rev. 0 PAGE 2 B. Water Effluent Concentration
- 1. Fission and activation gases in gaseous releases:
10 CFR 20, Appendix B, Table 2, Column 1
- 2. Iodine and particulates with half lives greater than 8 days in gaseous releases:
10 CFR 20, Appendix B, Table 2, Column 1
- 3. Liquid effluents for radionuclides other than dissolved or entrained gases:
10 CFR 20, Appendix B, Table 2, Column 2
- 4. Liquid effluent dissolved and entrained gases:
2.OE-04 uCi/ml Total Activity C. Average Energy Not applicable to Prairie Island regulatory limits.
D. Measurements and approximations of total activity
- 1. Fission and activation gases Total Gem +/-25%
in gaseous releases: Nuclide Gem
- 2. Iodines in gaseous releases: Total Gem +/-25%
Nuclide Gem
- 3. Particulates in gaseous releases: Total Gem +/-25%
Nuclide Gem
- 4. Liquid effluents Total Gem +/-25%
Nuclide Gem E. Manual Revisions
- 1. Offsite Dose Calculations Manual latest Revision number: _ _
Revision date : 9- I2-05
2005 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 3 1.0 BATCH RBLEASES (LIQUID)
QTR: 01 QTR: 02 QTR: 03 l QTRt 04 1.1 NUMBER OF BATCH RELEASES 3.10E+01 8.80E+01 2.008+01 2.OOE+01
- 1. 2 TOTAL TIME PERIOD (HRS) 5.55E+01 1.63E+02 3.48E+01 3.55E+01 1.3 MAXIMUM TIME PERIOD (HRS) 2.15B+00 3.63E+00 2.17E+00 1.98E+00 1.4 AVERAGE TIME PERIOD (HRS) 1.79E+00 1.85E+00 1.74B+00 1.78B+00 1.5 MINIMUM TIME PERIOD (HRS) 1.00B+00 7.50E-01 1.53B+00 1.52E+00
- 1. 6 AVERAGE MISSISSIPPI RIVER PLOW (CFS) 1.21E+04 3.82E+04 1.56e+04 2.48B+04 2.0 BATCH RELRAS8S (AIRBORNE)
QTR: 01 QTR: 02 QTR: 03 QTR: 04 2.1 NUMBER OF BATCH RELEASES 4.40B+01 3.50E+01 2.00B+00 0.00B+00 2.2 TOTAL TIME PERIOD (HRS) 1.09E+03 4.91E+02 3.40E+00 0.00B+00 2.3 MAXIMUM TIME PERIOD (HRS) 4.81E+01 2.40E+01 2.15B+00 0.00E+00 2.4 AVERAGE TIME PERIOD (HRS) 2.47E+01 1.40E+01 1.70B+00 0.00B+00 2.5 MINIMUM TIME PERIOD (HRS) 3.70E-01 4.28E-02 1.25E+00 0.00E+00 3.0 ABNORMAL RELEASES (LIQUID)
QTR: 01 QTR: 02 QTR: 03 QTR: 04 3.1 NUMBER OF BATCH RELEASES 0.00B+00 0.00E+00 0.0O0+00 0.00B+00 3.2 TOTAL ACTIVITY RELEASED (CI) 0.00B+00 0.00E+00 0.00B+00 0.OOE+00 3.3 TOTAL TRITIUM RELEASED (CI) 0.0o0+00 0.00B+00 0.00B+00 0.0O0+00 4.0 ABNORMAL RELEASRS (AIRBORNE)
QTR: 01 QTR: 02 QTR: 03 QTR: 04 4.1 NUMBER OF BATCH RELEASES 0.00B+00 0.00B+00 0.00B+00 0.00B+00 4.2 TOTAL ACTIVITY RELEASED (CI) 0.00B+00 0.00B+00 0.OOE+00 0.00B+00
2005 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 4 TABLE 1A GASEOUS EFF UENTS - SUMMATION OF ALL RZLEASS I QTR: 01 QTR2 02 QTR: 03 QTR2 04 5.0 FISSION AND ACTIVATION GASES 5.1 TOTAL RELEASE (CI) 0.00B+00 1.22B+01 3.63E-01 0.00Z+00 5.2 AVERAGE RELEASE RATE (UCI/SEC) 0.00B+00 1.55E+00 4.62R-02 0.00B+00 5.3 GAMMA DOSE (MRAD) 0.00B+00 5.50E-03 4.47E-05 0.00B+00 5.4 BETA DOSE (MRAD) 0.OOE+00 1.83E-02 2.86E-03 0.OOE+00 5.5 PERCENT OF GAMMA TECH SPEC (%) 0.OOE+00 5.50E-02 4.47E-04 0.00B+00 5.6 PERCENT OF BETA TECH SPEC (%) 0.OOE+00 9.13B-02 1.43B-02 0.00B+00 6.0 IODINJS 6.1 TOTAL I-131 (CI) 0.00B+00 J 8.33E-05 0.00B+00 0.OOE+00 6.2 AVERAGE RELEASE RATE (UCI/SBC) 0.OOE+00 1.06E-05 0.OOE+00 0.00E+00 7.0 PARTICUlrATES 7.1 TOTAL RELEASE (CI) 0.00B+00 2.09E-05 0.00B+00 0.OOE+00 7.2 AVERAGE RELEASE RATE (UCI/SBC) 0.OOE+00 2.66B-06 0.00E+00 0,00B+00 8.0 TRITIUM 8.1 TOTAL RELEASE (CI) 3.24E+00 3.33E+00 2.71B+00 3.30B+00 8.2 AVERAGE RELEASE RATE (UCI/SBC) 4.12B-01 4.24E-01 3.45B-01 4,20E-01 9.0 TOTAL IODINE, PARTICULATE AND TRITIUM (UCI/SEC) 4.12E-01 4.248-01 3.45E-01 4.20E-01 10.0 DOSE FROM IODINE, LLP, AND TRITIUM (MREM) 9.59E-03 1.73E-02 4.86E-03 5.91E-03 11.0 PERCENT OF TECH SPEC (%) 6.39E-02 1.16E-01 3.24E-02 3.94E-02 12.0 GROSS ALPHA (CI) 0.OOE+00 0.00E+00 0.0O0+00 0.OOE+00
2005 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE S TABLE IC GASEOUS EFFLUENTS - GROUND LEVEL RELEASES (CI) 13.0 FISSION AND ACTIVATION GABSE CONTINUIDUS MODE BATCH MODE NUCLIDZ lQTRs 01 QTR: 02 lQTRs 03 l QTR: 04 ll QTRs 01 IQTR: 02 l QTR: 03 l QTR: 04 l RR-85 CI 6.18E-O1 5.30E-03 1.23Z-01 3.42B-01 KR-85M CI 8.62B-05 XZ-131M CI 8.748-02 2.28E-02 2.47E-04 XE-133 CI 1.03B+01 3.40B-03 8.54Z-01 1.25E-02 XE-133M CI 1.51E-04 1.89B-OS 3.078-03 XB-135 CI 1.04B-01 6.80B-03 XE-135M CI 1.5 SE-os TOTALS CI 0.00B+00 1.12E+01 _ D.72D-03 0.OOE+00 0.00E+00 1.01E+00 3.55E-01 0.00B+00 14.0 IODINES CONTINUOUS MODE BATCH MODE INUCLIDE I QTRs 01 IQTRs 02 lOTR: 03 l QTR: 04 QTR: 01 QTR: 02 l QTR: 03 QTRs 04 X-131 l CI l8.33B-05 I-133 CI 1.81F-os TOTALS CI 0.00E+00 1.01B-04 0.00B+00 0.00E+00 0.00B+00 0.00E+00 l0.00+00 0.00E+00
2005 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 6 TABLE IC GASEOUS EFFLURNT - GROUND LEVEL RELEASES (CONTINUED) 15.0 PARTICULATES CONTINUOUS MODE BATCH MODE lNUCLID l UNITS I QTR$ 01 I QTR: 02 QTRt O:3 lQTR: 04 1 QTR:01 QTR: 02 lQTR: 03 l QTRt 04 l BE-7 Cl 9.268-07 Co-se CI 3.43B-07 CS-137 CI 2 I 1.94-05 SR-89 CI 2.09B-07 - 0.i TOTALS CI O.OOE+O0 1.48E-06 0.003+'DOJ 0.003+00 0.00R+00 1.94B-05 1O-OOE+OO l 008+00 I
2005 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 7 TABLR 1A LIQUID XFFLUNNTS - SUMMATION OF ALL RELRASRS QTR: 01 QTR: 02 QTR: 03 IQTR: 04 16.0 VOLUME OF WASTE PRIOR TO DILUTION (LITERS) 4.92E+07 5.11E+07 3.10E+07 3.39E+07 17.0 VOLUME OF DILUTION WATER (LITERS) 1.53E+11 1.08E+11 2.63E+ll 2.24E+11 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 TOTAL RELEASES W/O H-3, RADGAS, ALPHA (CI) 1.62B-02 f 5.35E-02 [ 1.09E-02 1.70E-02 ]
18.2 AVERAGE DILUTION CONCENTRATION (UCI/ML) 1.06E-10 [ 4.96E-10 4.15E-11 7.61E-11 19.0 TRITIUV 19.1 TOTAL RELEASE (CI) [ 1.44E+02 1.76E+02 9.32B+01 1.03E+02 ]
19.2 AVERAGE DILUTION CONCENTRATION (UCI/ML) 9.40E-07 1.638-06 3.54E-07 j 4.60E-07 ]
20.0 DISSOLVED AND WITRAIXND GASES 20.1 TOTAL RELEASE (CI) l 3.27E-04 1.54E-02 8.19B-05 3.36E-05 20.2 AVERAGE DILUTION CONCENTRATION (UCI/ML) 2.14E-12 1.43E-10 3.11B-13 1.50E-13 21.0 GROSS ALPHA (CI) 0.00B+00 I 0.00B+00 I0.00B+00 I 0.00E+00 22.0 TOTAL TRITIUM, FISSION & ACTIVATION PRODUCTS (UCI/ML) 9.408-07 1.63E-06 3.54B-07 4.60E-07 23.0 TOTAL BODY DOSE (MREM) 3.67B-04 4.87B-04 2.25E-04 2.52B-04 24.0 CRITICAL ORGAN 24.1 DOSE (MREM) 3.67B-04 1 l.918-03 2.25E-04 2.528-04 24.2 ORGAN TOT BODY GI TRACT TOT BODY TOT BODY 25.0 PERCENT OF TECHNICAL SPECIFICATIONS LIMIT (%) 1.22E-02 1.62E-02 7.50E-03 8.40B-03 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%) 1.22E-02 1.91E-02 7.50E-03 8.408-03
2005 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 8 TABLE 2A LIQUID rFFLUsiTs - SUMMATION Or ALL RELEASES (CI) 27.0 INDIVIDUAL LIQUID EFFLUENT CONTINUOU,s MODE BATCH MODE NUCLIDB QTRt 01 QTR: 02 OTR: 03 j QTR: 04 QTR 01 I QTRs 02 l QTR: 03 QTR: 04 AG-llON CI 1.00B-04 2.26E-03 6.31B-04 2.753-04 CO-57 CI 4.88B-05 1.173-04 7.783-06 4.473-05 6.983-03 1.493-02 1.103-03 1.383-03 CO-60 CZ 2.023-04 1.203-03 6.67E-04 6.593-04 CR-51 CI 1.28B-03 5.98E-0S CS-137 CI 7.24B-06 9.62F-07 FB-55 CI 4.87B-03 8.593-03 1.463-02 5.173-03 9.173-03 FB-59 CI 2.473-05 6.373-04 2.31B-OS I-131 CI 8.328-06 1.343-06 1-134 CZ 4.783-07 LA-140 CI 7,07B-06 MN-54 CI 3.313-06 5.023-05 3.383-05 2.11B-05 NA-24 CI 9.86B-07 6.503-07 NB-95 CI 1.05B-05 3.03B-04 4.76B-05 3.663-05 NB-95 CI 4.62B-06 NB-97 CI 3.31B-06 8.613-06 5.128-06 RU-105 CI 2.163-06 SB-124 CI 2.03B-05 1.893-03 2.183-04 3.263-05 SB-125 CZ 1.773-04 5.27B-03 8.803-04 4.943-04 SN-113 CI 8.57B-05 9.943-06 4.663-06 SR-90 CI 1.36Z -06 SR-92 CI 5.493-07 4.753-05 1.203-OS 7.183-06 TE-123M CI 3.43B-OS 3.103-04 5.703-OS 6.263-06 TR-125M CI 1.02B-02 1.97B-03 TE-127 CI 1. 06B-04 (CONTINUED)
2005 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 9 TABLE 2A LIQUID EFFLuRTS8 - SJNMATIOU OF ALL RELEABSE (CONTINUIKD) 27.0 INDIVIDUAL LIQUID EFFWLUUT CONTINUOUS MODE BATCH MODE lNUCLID QTR: 01 I QTR: 02 !QTR: 03 IQTRS 04 QTR: 01 QTR: 02 QTR: 03 QTRs 04 TB-129 CI 1.41B-05 TL-201 CI 2.753-06 W-187 CI 1.01B-05 3.483-06 zN-65 CI 3.04B-06 2.31B-06 ZR-95 Ce 6.17B-06 1.87B-04 2.85E-05 1.193-05 ZR-97 CI 1.15B-06 TOTALS CZ 1.563-05 9.623-07 10.003+011 4.88B-03 1.62B-02 5.358-02 1.09B-02 1.21B-02 28.0 DISSOLVED AND ENTRAINUD CASES CONTINUOUS MODE BATCH MODE I NUCLIDB lUNITS l]1 QTRs 02 QTR: 03 QTRS 04 1 QTR: 01 I QTRs 02 _ QTR: 03 l QTRs 04 l XB-131M CI 6.83B-04 l XB-133 CI 3.27B-04 1.473-02 8.193-05 3.363-05 7 XB-133M CI 1.08B-05 TOTALS CI 0.00B+00 I0.003+00 0.003+00 0.003+00 I l 3.273-04 l 1.54B-02 8.193-05 l 3.363-05 1
ENCLOSURE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January 01, 2005 - December 31, 2005 8 pages follow
PINGP 753, Rev. 7 Page 1 of 8 Retention: Life PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01/01/05-12/31/05 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)
- 1. Solid Waste Total Volumes and Total Curie Quantities:
m 179.4 ft3 3.78E+03 135.8 Ci 2.37E+02 94 B. Dry-Compacted mf3 ft3 Ci C. Non-Compacted m3 7.43E+02 1280 2.62E+04 258 1.52E+00 2.50E+01 94 ftCi3 D. Filter Media ft3 m3 S. Other (furnish description) m 5.54E+01 - 1958 Ci U2 Rx Head 1.96E+03 ci 2.32E+01 2.50E+01 The solid waste information provided in this report is the volume and activity of the low-level waste leaving the Prairie Island site.
No allowance is made for off-site volume reduction prior to disposal.
Document4
PINGP 753, Rev. 7 Page 2 of 8 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01-01-05/12-31-05 NORTHERN STATES POWER License No. DPR42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) [continued]
- 2. Principal Radionuclide Composition by Type of Waste:
(Bold letter designation from Page 1)
TYPE Percent %
Abundance Nuclide (0.00E0)
C *Fe-55 6.28E+01 Co-58 8.73E+00 Co-60 7.83E+00
- Ni-63 1.1OE+01 Zr-95 2.08E+00 Nb-95 2.69E+00 Cr-51 1.05E+00 I % cutoff S *Fe-55 3.93E+01 Co-58 4.01 E+01 Co-60 8.31 E+00 Fe-59 1.03E+00 Zr-95 1.05E+00 Cr-51 5.30E+00
- Ni-63 2.55E+00 1% cutoff
- = Inferred - Not Measured on Site
PINGP 753, Rev. 7 Page 3 of 8 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01-01-05112-31-05 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) [continued]
- 2. Principal Radionuclide Composition by Type of Waste (Continuation):
(Bold letter designation from Page 1)
TYPE Percent %
Abundance Nuclide (0.OOE0)
A *H-3 1.1 OE+00
- Fe-55 1.52E+01
- Ni-63 2.74E+01 Co-60 1.22E+01 Cs-1 34 1.17E+01 Cs-1 37 2.83E+01 11%cutoff
- = Inferred - Not Measured on Site
PINGP 753, Rev. 7 Page 4 of 8 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01-01-05/12-31-05 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) [continued]
- 3. Solid Waste Disposition:
Number of Shipments Mode Destination 14 RACE Logistics RACE, LLC 2 Hittman Envirocare of Utah (Bulk) 2 Perkins Envirocare of Utah (Bulk) 2 R & R Trucking Envirocare of Utah (Containerized) 6 R & R Trucking ALARON Corporation 2 Hittman Barnwell Waste Management Facility 1 R & R Trucking Barnwell Waste Management Facility
PINGP 753, Rev. 7 Page 5of8 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01-01-05/12-31-05 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) [continued]
- 4. Shipping Container and Solidification Method:
Disposal No. Volume Activity Type of Container Solidif.
(Ft3/m3) (mCi) Waste Code Code 05-009 179.4/5.08 2.09E+04 A N/A 05-010 179.4/5.08 4.50E+02 A N/A 05-011 179.4/5.08 2.62E+02 A N/A 05-013 179.4/5.08 2.25E+02 A N/A 05-015 179.4/5.08 2.37E+02 A N/A 05-016 179.4/5.08 3.12E+02 A N/A 05-017 179.4/5.08 4.50E+02 A N/A 05-018 2560/72.4 5.88E+01 C N/A 05-019 1280/36.2 5.14E+00 C N/A 05-039 260/7.36 5.27E-02 C N/A 05-045 2560/72.4 4.47E+02 c N/A 05-032 1958/55.44 2.32E+04 S N/A 05-046 2560/72.4 1.76E+02 C N/A 05-047 2560/72.4 1.OOE+01 C N/A 05-048 1280/36.2 1.05E+01 C N/A 05-052 135.8/3.85 9.OOE+04 A N/A 05-053 135.8/3.85 7.08E+04 A N/A 05-057 1410/39.9 1.07E+02 c N/A 05-058 1410/39.9 7.70E+01 C N/A 05-059 1410/39.9 2.02E+02 C N/A 05-060 1410/39.9 2.02E+02 C N/A 05-061 2560/72.4 1.76E+01 C N/A 05-062 1280/36.2 1.05E+01 C N/A 05-064 940/26.6 7.OOE-02 A N/A 05-065 949.6/26.9 1.90E-01 A N/A 05-068 2560/72.4 2.35E+02 C N/A 05-070 1128/31.9 4.92E+01 C N/A 05-071 179.4/5.08 8.60E+01 A N/A 05-072 179.4/5.08 5.32E+04 A N/A TOTAL 29 31958/905 2.62E+05 S
CONTAINER CODES: L LSA (Shipment type) A Type A B Type B Q Highway Route Controlled Quantity
PINGP 753, Rev. 7 Page 6 of 8 SOLIDIFICATION CODES: C = Cement TYPES OF WASTES: A = Resins B = Dry Compacted C = Non-Compacted D = Filter Media S = Other
PINGP 753, Rev. 7 Page 7 of 8 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01-01-05/12-31-05 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)
Number of Shipments Mode Destination 0
PINGP 753, Rev. 7 Page 8 of 8 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01-01-05/12-31-05 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS C. PROCESS CONTROL PROGRAM CHANGES TITLE: Process Control for Solidification/Dewatering of Radioactive Waste from Liquid Systems Current Revision Number: 8 Effective Date: 8/25/1999 If the effective date of the PCP Is within the period covered by this report, then a description and justification of the changes to the PCP is required I (T.S.6.5.D) L . Attach the sidelined pages to this report.
Changes/Justification: N/A
ENCLOSURE 4 OFFSITE DOSE CALCULATION MANUAL (ODCM)
REVISION 19 EFFECTIVE DATE: 9112/05 221 pages follow